棒束通道内温度场分布特性研究

可视化实验技术越来越多地被应用于核反应堆系统参数的测量,本文基于激光诱导荧光（LIF）技术的特点,介绍该技术的难点和解决方案,并对棒束通道定位格架下游稳态流和脉动流下温度分布进行了研究。结果显示,通过对系统光学特性和染色剂特性研究,可提高LIF技术的应用范围和测量精度。同时采用后处理技术,可获得更准确的温度场分布。通过对棒束通道定位格架下游全场温度进行测量,获得了稳态流和脉动流两种工况下温度的分布。定位格架能显著增强下游的流动搅混,提高换热能力。流速的波动也会对温度分布产生显著影响。研究表明,LIF技术可实现对棒束通道内流体温度分布的全场测量,根据温度分布特性研究可实现对定位格架性能的评价。     

棒束通道温度场可视化实验研究

基于激光诱导荧光技术,对带定位格架棒束通道的温度场进行了可视化实验研究。采用折射率匹配技术,搭建可视化实验系统,提出适用于棒束通道温度场点对点标定的关系式,利用此关系式对定位格架下游温度场进行了重构。实验结果显示,采用激光诱导荧光技术可获得定位格架下游全场温度分布。分析了不同加热形式、流量和热流密度对温度分布的影响,并采用轴向流体温差和温度分布不均匀性定量评价了定位格架下游的搅混能力。在定位格架下游0～4D_h范围内,搅混性能逐渐增大,在4D_h后会随高度的增加逐渐减小。结果表明,激光诱导荧光技术可适用于棒束通道温度场的非介入式、全场测量,有助于对相应程序的验证和定位格架搅混性能的评价。     

激光诱导荧光技术对棒束通道内定位格架搅浑特性研究

基于激光诱导荧光（LIF）技术开展了5×5棒束通道内定位格架搅浑特性的可视化研究。常温常压下,通过示踪染色剂（RhB）浓度分布表征流体微团的搅浑行为,清晰展现染色剂溶液在定位格架作用下的搅浑扩散过程,获取格架下游流场的搅浑信息。采用自验证方法分析验证LIF技术测量的准确性,重构棒束通道内径向与轴向染色剂浓度分布,对比带定位格架与不带定位格架的实验结果,得到定位格架对其下游流场的影响范围及不同棒束子通道所受搅浑程度的差异,并以变异系数量化格架对流场搅浑性能的强弱。实验结果表明：定位格架能快速搅浑流动工质,其搅浑翼片分布形式的差异是造成不同子通道交叉搅浑强弱及各向异性的主要原因。本实验工况（Re＝10 478）下,格架对其下游流场的作用范围约为8倍当量直径(D_h),流动工质在格架下游5D_h附近所受搅浑最为剧烈。     

脉动流下定位格架下游时均流场分布特性研究

研究流量波动下棒束通道内定位格架下游瞬时流场演变特性对于揭示海洋条件下燃料组件内流动换热机理具有重要意义。本文应用粒子图像测速（PIV）技术获得了脉动流下棒束通道内定位格架下游时空演变流场结构,分析了脉动参数（脉动周期和脉动振幅）对定位格架下游速度分布和湍流特性的影响。结果表明,脉动流下定位格架下游时均速度与定常流动下时均速度差异较小,且基本不随脉动振幅和脉动周期变化而变化;脉动流下的定位格架下游横向速度和轴向速度均方根与定常流动下的速度均方根存在明显差异,且随脉动参数变化呈现出不同的变化趋势。本文研究结果有助于揭示燃料组件在非稳态条件下瞬态特性,并为燃料组件的设计和优化奠定基础。      

冷却剂与含格架燃料棒束多场耦合分析

燃料棒束作为压水堆燃料组件的组成部分,其热工和结构特性直接关系到反应堆的安全。本文利用ANSYS WORKBENCH软件分析了冷却剂在5×5含定位格架燃料棒束通道内流动的分布,采用冷却剂与燃料棒束多场耦合的方式研究了燃料棒束的流动传热特性和结构形变特性。结果表明：定位格架扰动冷却剂形成横向二次流并在下游棒束间形成绕流;多场耦合条件下二次流峰值速度和平均速度均小于单流场的;二次流与燃料棒的热应力使棒束发生形变,功率和流动分布的不均匀导致形变在轴向和径向的不均匀;相较于无格架情况,定位格架的存在使冷却剂的搅混流动更加明显,冷却剂对燃料棒冲击增大;在有、无定位格架两种情况下棒束形变均很小,可保持原本结构的稳定。     

脉动流下棒束通道内相位差及瞬态流场研究

事故条件及海洋条件下反应堆处于非稳态工况,堆芯燃料组件内热工水力行为具有瞬变及多因素耦合特性,对反应堆的安全提出更高挑战,因此有必要对燃料组件内瞬态特性进行研究。本文通过测量棒状燃料组件内压降和流量之间延迟时间开展棒束通道脉动流条件下相位差研究,对比了相位差在不同振幅、不同流动状态下的变化特性,并分析了定位格架对脉动流相位差的作用特点。另外,基于粒子图像测速（PIV）技术开展了脉动流条件下棒束通道内流场分布特性研究,对比了相同流量条件下稳态工况与瞬态工况下流场分布差异,分析了主流具备不同加速度时棒束通道内流场分布特征。实验结果表明：定位格架可减小脉动流下棒束通道内相位差;棒束通道内流场演化滞后于主流量变化。实验结果有助于揭示燃料组件在非稳态条件下瞬态特性,并为燃料组件的设计和优化奠定基础。     

Flow Characteristics in Spacer Grids Measured by Rod-embedded Fiber Laser Doppler Velocimetry

Precise measurement of velocity in fuel bundles is required to improve the thermal-hydraulic properties of Pressurerized Water Reactor (PWR) spacer grids. To better understand the cross-flow characteristics in rod bundles for developing spacer grids, we used the rod-embedded fiber laser Doppler velocimetry (rod LDV) to measure the flow velocities inside the spacer grid flow channels. As the result of measurement, we found that the flow distribution inside the spacer grid depends on the local flow resistance of the grid straps and is clearly affected by the presence of a mixing vane. We also clarified the relationship between cross-flow velocity in the fuel bundle downstream of the spacer grid and the axial flow inside the spacer grid.     

棒束通道内定位格架搅混特性PIV可视化研究

定位格架作为燃料组件中重要的组成部件之一,不仅在结构上固定燃料棒,而且在燃料组件内热工水力性能同样显著,特别是对工质的搅混性能直接关系到反应堆的经济性和安全性,因此有必要对燃料组件内定位格架搅混特性进行研究。本文通过粒子图像测速（PIV）技术开展了棒束通道内定位格架上下游流场的可视化研究,对比了有无格架棒束通道内流场的分布特征,定量分析了定位格架对棒束通道流场搅混的贡献。对不同流速下定位格架下游横纵速度的沿程变化特性进行研究,发现了不同流速作用下定位格架对横向、轴向速度的促进和抑制规律。另外,通过速度均方根对下游的湍流特性进行了评估。实验结果可为数值计算提供全场的数据验证,并可为定位格架设计和优化提供基础。     

十字焊点对定位格架水力特性影响的数值研究

作为定位格架重要的结构特征之一,其内条带间的十字焊点的形状与定位格架的强度及水力特性密切相关。为深入研究该十字焊点形状对定位格架水力特性的影响规律,以5×5燃料组件定位格架为研究对象,采用ANSYS CFX12.1对燃料棒束通道内的流动现象进行数值模拟研究,得到了通道内的流场分布。研究结果表明:增加十字焊点直径能削弱格架下游近格架区域子通道内冷却剂的涡流强度以及子通道间的搅混强度,同时增强格架下游远格架区域子通道内的涡流强度以及子通道间搅混强度;增加十字焊点直径对格架下游子通道内的搅混强度影响较小;定位格架的形状阻力系数随十字焊点直径的增大而增加。以上结果说明采用较大直径的十字焊点可使定位格架下游区域的换热能力趋于均衡,从而使堆芯温度分布更加均匀,但同时也会产生较大的压力损失。     

带MVG和MSMG的5×5全长棒束单相流场和温度行为数值分析

定位格架作为燃料组件的关键部件之一,直接影响到燃料组件的热工性能。本文对带结构格架（MVG）和跨间搅混格架（MSMG）的5×5全长加热棒束单相流场和温度场采用计算流体力学（CFD）程序进行数值分析研究,获得该特征棒束组件出口二次流场以及温度场分布特性。研究表明,定位格架下游流场受定位格架和距离的影响,定位格架上游流场对下游二次流几乎无影响,定位格架导致流体强烈的横向二次流,增强了流体和加热棒之间的换热能力,使得棒束子通道截面流体温度更加均匀。与5×5全长棒束出口子通道温度的实验数据对比分析表明,获得的计算模型可以较好地分析该型棒束组件结构温度场行为。      

脉动流下棒束通道内流场与湍流特性的PIV实验研究

事故条件下路基核反应堆以及受到海洋条件附加惯性力影响的浮动核反应堆一回路冷却剂会处于非稳定流动状态,进而改变冷却剂的流动和传热特性,影响反应堆的安全运行。本文应用锁相粒子图像测速（PIV）以及折射率匹配技术分别对脉动流条件下有无定位格架棒束通道内瞬时速度进行了测量。实验结果表明：对于不带定位格架的棒束通道,加速使得靠近通道壁面附近流体速度变大,而靠近中心区域流体速度变小。此外湍流强度分量随流体加速而逐渐变小,随流体减速而逐渐增加。对于流向压力梯度驱动的周期性脉动流,横向脉动速度均方根分量u′滞后于流向脉动速度均方根分量v′,且二者都滞后于流速的变化;对于带定位格架的棒束通道,带有搅浑翼的定位格架强烈的交混作用极大地减小了流体加速度对棒束通道内速度分布和湍流强度带来的影响。实验结果有助于更加清晰地揭示脉动流在棒束通道中的作用机理。     

Numerically simulating the thermal-hydraulic characteristics within the fuel rod bundle using CFD methodology

With the dramatic progress in the computer processing power, computational fluid dynamics (CFD) methodology can be applied in investigating the detailed knowledge of thermal-hydraulic characteristics in the rod bundle, especially with the spacer grid. These localized information, including flow, turbulence, and heat transfer characteristics, etc., can assist in the design and the improvement of rod bundles for nuclear power plants. In this paper, a three-dimensional (3D) CFD model with the Reynolds stresses turbulence model is proposed to simulate these characteristics within the rod bundle and subsequently to investigate the effects of different types of grid on the turbulent mixing and heat transfer enhancement. Two types of grid designs are used herein, including the standard grid and split-vane pair one, respectively. Based on the CFD simulations, the secondary flow can be reasonably captured in the rod bundle with the grid. The split-vane pair grid would enhance both the flow mixing and the heat transfer capability more than the standard grid does, as clearly shown in the simulation results. In addition, compared with the results of experiment and correlation, the present predicted result for the Nusselt (Nu) number distribution downstream the grid shows reasonable agreement for the standard grid design. However, there is discrepancy in the decay trend of Nu number between the prediction and measurement for the split-vane pair gird. This would be improved by adopting the finer mesh (y⁺ < 1) simulation and Low-Reynolds form turbulence model, which is our future research work.     

反应堆棒束通道搅混翼数值研究

定位格架上的搅混翼是核反应堆燃料组件中的关键部件,其性能对棒束通道热工水力特性有重要的影响。以带单层定位格架的5×5棒束为研究对象,对搅混翼排布方式及末端形状对格架下游的流场和温度场的影响进行数值模拟研究。计算结果表明,改变搅混翼的排布方式,压降几乎不受影响,但格架下游流场和传热情况却因排布方式的改变而发生显著变化;将搅混翼末端形状改为弧形,压降较典型撕裂型搅混翼没有明显差异,但换热情况得到明显改善。      

带定位格架棒束通道内两相流型研究

在空气-水两相流动工况下,将RBI光学探针测得的时序波形和目测相结合,对AFA-2G 33定位格架组成的棒束通道内存在的两相流型进行了识别。通道水力当量直径为8.98mm,元件的棒径为9.5mm,栅距为12.6mm,棒壁距为2.65mm。液相和气相表观速度范围分别为0.40-2.69m/s,0.02-2.99m/s。试验获得了流型图。结果表明,定位格架结构,特别是交混叶片对定位格架附近区域两相流型变化有重要影响,在棒束通道内的同一截面上存在不同种类流型。     

定位格架下游湍流特性测量研究

在子通道雷诺数为6 600、13 200、26 400和39 600下,使用粒子成像测速仪对5×5棒束分流型交混翼定位格架下游横向和纵向流动进行测量。平均速度和湍流脉动速度均方根的实验结果最大不确定度低于1%的主流平均速度。格架下游二次流结构经历了交混翼脱落涡结构耗散、剪切产生双涡结构、双涡结构向单涡结构的转变及单涡结构沿程衰减过程,横向平均速度和湍流脉动速度均方根沿程变化均受涡结构演进影响。格架近场湍流统计量迅速衰减;格架远场湍流统计量缓慢衰减,流动趋于光棒束充分发展流动。横向流动受雷诺数效应和格架交混效应共同影响。     

压水堆棒束定位格架两相搅混特性数值研究

本文提出一种CFD方法用于评价压水堆燃料棒束定位格架两相搅混特性。针对两种典型的定位格架,采用CFX12.0进行了空气-水两相流动的数值模拟,并与采用氟里昂工质开展的临界热流密度（CHF）实验进行对比。结果表明,CFD方法可初步应用于评价格架下游汽泡的分布特性。     

Non-intrusive experimental investigation of flow behavior inside a 5 × 5 rod bundle with spacer grids using PIV and MIR

The validity of the simulation results from computational fluid dynamics (CFD) is still under scrutiny. Some existing CFD closure models for complex flow produce results that are generally recognized as being inaccurate. Development of improved models for complex flow simulation requires an improved understanding of the detailed flow structure evolution with dynamic interaction of the flow multi-scales. Thus, the goal of this work is to contribute to a better understanding of presupposed and existent events that could affect the safety of nuclear power plants. The fundamental phenomena of fluid flow in rod bundles with spacer grids can be elucidated by using state-of-the-art measurement techniques. This study aims to develop an experimental data base with high spatial and temporal resolution of fluid flow velocity inside a 5 × 5 rod bundles with spacer grids. The full-field detailed data base is intended to validate CFD codes at various temporal-spatial scales. Measurements are carried out using dynamic particle image velocimetry (DPIV) technique inside an optically transparent rod bundle utilizing the matching index of refraction (MIR) approach. This work presents full field velocity vectors and turbulence statistics for a rod bundle under single phase flow conditions.     

Experimental and numerical simulation of air-water two-phase flow in the rod bundle with grid spacer

1 Introduction Grid spacer is the key part of reactor fuel assem-bly. The presence of spacers in fuel assemblies affectsvarious thermal-hydraulic characteristics of the reactorcore. The grid spacer with fine performance can im-prove thermal-hydraulic performance of the core fuelassembly and enhance the critical heat flux withouttoo much augment of the pressure loss. As a result,the implementation of grid spacer with high thermalperformance provides more thermal margin, then in-creases s…     

Experimental observation of the droplet size change across a wet grid spacer in a 6 × 6 rod bundle

During the reflood phase of a postulated loss of coolant accident in a nuclear reactor, entrainment of liquid droplets can occur at a quench front of reflooding water. It is widely recognized that the behavior of the entrained droplets crucially affects the reflood heat transfer phenomena by decreasing the superheated steam temperature and interacting with a rod bundle and spacer grids. For this reason, various experimental and numerical studies have been performed to examine droplet behavior such as the droplet size, velocity and droplet fraction inside a rod array. In this study, an experiment on the droplet behavior inside a heated rod bundle has been performed. The experiment was focused on the change of droplet size induced by a spacer grid in a rod bundle geometry, which results in the change of the interfacial heat transfer between droplets and superheated steam. A 6 × 6 rod bundle test facility in Korea Atomic Energy Research Institute was used for the experiment. Steam was supplied by an external boiler into the bottom of the test channel, and a droplet injection nozzle was equipped instead of simulating a quench front of reflooding water. The major measuring parameters of the experiment were the droplet size and velocity, which were measured by a high-speed camera and a digital image processing technique. A series of experiments were conducted with various flow conditions of a steam injection velocity, heater temperature, droplet size, and droplet flow rate. The experiments provided the data on the change of the Sauter mean diameter of droplets after collision with a wet grid spacer depending on flow conditions.     

Experimental investigation of turbulent flow through spacer grids in fuel rod bundles

This paper contains experimental data of pressure, velocity and turbulence intensity in a 24-rod fuel bundle with spacer grids. Detailed pressure measurements inside the spacer grid have been obtained by use of a sliding pressure-sensing rod. Laser Doppler Velocimetry technique was used to measure the local axial velocity and its fluctuating component upstream and downstream of the spacer grid in sub-channels with different blockage ratios. The measurements show a changing pattern in function of radial position in the cross-section of the fuel bundle. For sub-channels close to the box wall, the turbulence intensity suddenly increases just downstream of the spacer and then gradually decays. In inner sub-channels, however, the turbulence intensity downstream of the spacer decreases below its upstream value and then gradually increases until it reaches the maximum value at approximately two spacer heights. The present study reveals that spacer effects, such as local pressure distribution and turbulence intensity enhancement, not only depend exclusively on the local geometry details, but also on the location in the cross-section of the rod bundle.